【摘 要】
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Irradiation-induced hardening and premature fracture are major concerns for the intermediate-temperature application of high Cr ferritic/martensitic steels as structural materials in nuclear reactors
【机 构】
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State Key Laboratory for Turbulence and Complex System,Department of Mechanics and Engineering Scien
【出 处】
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第13届中日双边先进能源系统和聚变裂变工程材料会议(CIS-13)
论文部分内容阅读
Irradiation-induced hardening and premature fracture are major concerns for the intermediate-temperature application of high Cr ferritic/martensitic steels as structural materials in nuclear reactors below 300~3500C.The microstructure changes at the sub-nanometre scale in irradiated Fe-Cr alloys have been studied extensively.In the range of low to moderate irradiation doses(0.1~1dpa),several types of irradiation-induced defects have been identified,namely,(i)dislocation loops(DLs)of size up to ten nm,(ii)α clusters(Cr rich precipitates)of size not exceeding several nanometres,(iii)sub-nanometre vacancy clusters containing several point defects,and(iv)SRCs(NiSiPCr-enriched clusters)of a few nanometres.In this work,we proposed a theoretical model for the thermo-mechanical plastic response of Fe-Cr alloys accounting for the neutron irradiation induced defects at elevated temperatures.
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